Latest Fusion R&D Activities at INEST
Presented by Prof. Yican Wu (Director-General of INEST)
Contributed by FDS Team Institute of Nuclear Energy Safety Technology ( INEST ) Chinese Academy of Sciences ( CAS ) www.fds.org.cn Outline
I. Brief Introduction to INEST
II. Highlights of Fusion R&D Activities
III. Summary History of INEST FDS Team
ASIPP ASIPP Fusion-Fission Reactor Technology INEST FDS Team Hybrid Division Division Frontier Development of Science 2017 (>500 Persons)
1986 2003 2012 (~50 Persons)
Fusion Driven-subcritical System Fusion Design Study Fission/Fusion Design Study
Fusion Digital Simulation 1986 2006 2011
High-Tech Program ITER Program ADS Program
*ASIPP: Institute of Plasma Physics, CAS Personnel
Employees： Students: • Staff：~400 • Postgraduates：~100 • Guest scientists: ~50
Current members：>500 Orientation of INEST
• The professional institute focuses on design and R&D of advanced nuclear energy systems and safety technologies, and aims to be 1. The International center for nuclear safety research
2. The national education center for nuclear safety 3. The professional supporting center of nuclear safety technology for power plants and facilities
• The independent nuclear safety evaluation center. Scientific Programs at INEST
Under Three National Mega-Programs: • Strategic Priority Research Program of CAS • ITER Related International & Domestic Program • Nuclear Energy & Safety Technology Innovation Program
Carrying Out Four Types of Research Projects: • Physics & Safety of Nuclear Energy • Lead-based reactors (GEN-V, ADS, SMR, etc.) • Fusion nuclear technology & materials • Nuclear technology applications Outline
I. Brief Introduction to INEST
II. Highlights of Fusion R&D Activities
• Fusion Neutron Sources
• Neutronics Methodology and Simulation
• Fusion Safety
• TBM and Related Technologies
III. Summary 1. Fusion Neutron Sources HINEG-I: Fusion-Fission Hybrid Neutron Source
Applications: Steady Beam: V&V of neutronic method and software, etc. Pulse Beam: Nuclear data measurement, etc.
Fusion neutrons with yield up to 6.4×1012n/s have been generated HINEG-I Main Sub-systems
Ion Source and Low Energy Beam Transportation Steady Beam Line
Rotating Target Control Room Fusion Neutron Driven Hybrid Nuclear Energy System Testing Facility : CLEAR-A0
CLEAR-0 HINEG-I CLEAR-A0 Lead-based Fusion Neutron Subcritical/critical Zero Hybrid Neutronics Source Power Reactor Testing Facility
The construction of CLEAR-A0 was finished in the early of 2017 HINEG-II: High Intensity Steady Neutron Source ( Preliminary Scheme )
Neutron yield：1015-1016 n/s
Conceptual Design Option Objectives
Materials Irradiation Neutronics Performance Test
R&D for key components of HINEG-II is on-going HINEG-III Conceptual Design Based on Gas Dynamic Trap
Two Options: . GDT-VFNS: Fusion Materials and Component Testing facility . GDT-Hybrid: Fusion-Fission Hybrid System
GDT-VFNS GDT-Hybrid
IAEA Coordinated Research Project F1.30.15 2. Neutronics Methodology and Simulation Super Multi-functional Calculation Program for Nuclear and Radiation Simulation: SuperMC
published by Springer 2017
Full functional neutronics calculation for transport, depletion, activation, dose etc CAD/Image-based accurate automatic modeling for complex irregular geometry Intelligent data analysis based on multi-D/multi-style visualization Network-based access on cloud computing platform Widely Used Worldwide
Application in 30+ Major Nuclear Projects • Europe：International Thermonuclear Experimental Reactor (ITER), Joint European Torus (JET), Wendelstein 7-X stellarator • USA：Facility for Rare Isotope Beams • CHINA：HPR1000, Experimental Advanced Superconducting Tokamak (EAST)
60+ Countries
Indexed by OECD/NEA: www.oecd-nea.org/tools/abstract/detail/iaea1437 Application Example 2017
Production of Activation Data Handbook for ITER Objective: Predict the activation of materials for accelerating the procedure of ITER neutronics studies without running codes The activation data handbook using SuperMC . Activation data: 90 natural elements (H-U), 17 widely used materials, neutron spectra at 6 typical locations (upper cryostat, rear of equatorial port, beneath lower port extension, cryostat basement, port cell, neutral beam cell) . Activation properties: activity, dose, decay heat, ingestion dose, transmutation graph, main contribution to activity, photon spectrum . Interface program for easy activation assessment
304 304LN
10 316L 10 316LN 109 Alloy718 JJ1 8 10 XM-19 107 106 105 104
103 activity (Bq/kg) 102 101 100 100 101 102 103 104 105 106 107 108 109 cooling time (secs) transition graph of Fe due to Activity of typical materials activation at the rear of Activation results of 316L in upper cryostat equatorial port 3. Fusion Safety （Magnetic D-T Tokamak） Combination of International Efforts
IEA Framework . Technology Collaboration Program (TCP) on a Co-operative Program on Environmental, Safety and Economic Aspects of Fusion Power (ESEFP)
ExCo Members Subtasks . China: Y. Wu, INEST . Task 1 In-vessel Tritium Source Terms . Task 2 Transient Thermo-fluid Modeling . Europe: D. Maisonnier, EC and Validation Tests . Japan: Y. Sakamoto, QST . Task 3 Activation Production Source Terms . Korea: K. Kim, NFRI . Task 4 Safety System Study . Russia: A. Kalashnikov, ROSATOM Methodology . Task 5 Failure Rate Database . USA: D. Clark, DOE . Task 6 Radioactive Waste Study . Task 7 Socio-Economic Aspects of Fusion Power . Task 8 Magnet Safety . Task 9 Fusion Power Plant Studies 2nd International Workshop on ESEFP (23rd Sept. 2017, Kyoto, Japan)
Exchange of latest progress in fusion safety Discussion: • Quantitative Safety Assessment of Fusion Power Plants • Fusion Safety Issues and Impact on Design and R&D Needs (ISFNT-13 Plenary) Agree to further enhance the international collaboration May organize the 3rd workshop in 2019 Fusion Energy to be the Ideal Nuclear Energy Source (From Safety Perspective)
ORE: as lower as possible Operational & Maintenance - lower than that of current PWR; Accident: no damage to public Accidental - Elimination of off-site evacuation; Radioactive waste: no burden to future generations of people - Can be recycled after limited period; Decommissioning Nuclear proliferation: no potential to produce weapon material
- Higher technical barrier for malicious utilization Non-proliferation
It is necessary to review the safety of the D-T tokamak FPP based on current state of knowledge, and provide in-depth suggestions for fusion safety towards ideal nuclear energy source Identification of Safety Gaps for Magnetic Fusion DEMO Reactors (2015~2017)
Combination of International Energy Agency (IEA) Technology Collaboration Program (TCP) on Environmental, Safety, and Economic aspects of Fusion Power (ESEFP)
• Reviewed DEMO safety issues and safety approach, and the international DEMO safety R&D activities. • Presented safety R&D gaps
Y. Wu, Z. Chen, L. Hu, M. Jin, Y. Li, J. Jiang, J. Yu, C. Alejaldre, E. Stevens, K. Kim, D. Maisonnier, A. Kalashnikov, K. Tobita, D. Jackson & D. Perrault. Identification of safety gaps for fusion demonstration reactors. Nature Energy 1, 16154, doi:10.138/nenergy.2016.154 (2016). Quantitative Safety Assessment of Fusion Power Plants
Aims to investigate: 1. what can we learn from the existing PWR safety demonstration? 2. what can we do to make fusion energy the ideal nuclear energy source?
PWR Model (AP1000) FPP Model (PPCS Basis)
• Core power/ Unit size (GWe) 3.40 / 1.1 • Fusion power / Unit size (GWe) 3.41 / 1.45 • Major / Minor radius (m) 7.5 / 2.5 • Active fuel length 4.3 m • Structure / PFM Eurofer / tungsten • Average linear power 5.71kW/ft • Blanket Coolant PbLi/ He/ Water TM • Fuel / Clad UO2/ZIRLO • Divertor Coolant He/ Water
The preliminary findings were reported in ISFNT-13 as a plenary. More detailed work is still on-going. 4. TBM and Related Technologies The Role of INEST in CN ITER TBM Program
Leading the R&D of CN DFLL TBM (Liquid Breeder) In Charge of CN HCCB TBM ( Solid Breeder) on Structure Materials, Safety Technology, etc.
PD phase of CN HCCB TBM Program officially started at 2016 Development of China Low Activation Martensitic steel: CLAM candidate structural material for CN ITER TBM
Nominal composition: 9Cr-1.5W-0.2V-0.15Ta-0.45Mn-0.1C 18-ton (3 ingots) smelting: good control of composition (2017) High-dose neutron irradiation experiments Spallation neutron irradiation~ 21dpa, Fission neutron irradiation ~3 dpa
YS Unirradiated 200 700 HEAT 0912 US Unirradiated 650 YS 2.5dpa/300℃ 180 US 2.5dpa/300℃ 600
MPa 160
550
Stress， 500
140 Strength (MPa)
450 Plates Rectangular 120 10 100 1000 400 0 50 100 150 200 250 300 Rupture time，h tube Temperature (℃) Nuclear Reactor Material Forging ingot Creep test ~10,000 hrs Neturon Irradiation Database (NRMD)
2017, industry standardization in China and code qualification for RCC-MRx of CLAM steel have made steady progress, with breakthroughs such as the approval of Material Specification by ANB. LiPb/He-Dual Coolant Fusion Blanket/Safety Test Loop: DRAGON-V
To support the design validation of DEMO blanket with the parameters covering the requirements of China ITER-TBM and CFETR.
Experimental functions
MHD effect Heat transfer Material corrosion under strong magnetic field
Main design parameters
Max. temperature: 1100℃ Max. flow rate of PbLi: 40kg/s Helium pressure: 10.5MPa
In 2017, DRAGON-V was constructed and operated with the highest temperature of 500℃ Accident Evolution/Verification Testing Facility
Experimental functions
Vapor explosion of lead-based alloys contacting with water
Steam bubble transportation monitoring
In-box LOCA
Heat-exchanger technique validation
Main parameters Temperature : 200~550℃
Max Pressure of the vessel: ~25MPa
Lead-based alloys inventory: ~3t Summary
1. In the field of fusion research, INEST concentrates on the Nuclear Technology and Safety, as it is indeed the key to finally realize the fusion as the ultimate energy source.
2. In 2017, INEST has achieved many milestones on HINEG neutron source, Neutronics Theory and SuperMC Software, Fusion Safety, and TBM Program, etc.
3. INEST is always open to domestic & international Cooperation. FUNFI-3 3rd International Conference on Fusion Neutron Sources and Subcritical Fission Systems 19-21 Nov. 2018, Hefei, China, hosted by INEST, CAS FUNFI3: Chairman: Yican Wu
An outstanding exchange platform on most Co-Chairman (preliminary): recent advancements in various aspects of A. Pizzuto (IT) fusion neutron sources and subcritical systems W. Stacey (USA) FUNFI1: 2011, Varenna, Italy, ENEA A. A. Ivanov (RUS) FUNFI2: 2016, Rome, Italy, ENEA Conference Topics International Advisory Committee A. Pizzuto, F. P. Orsitto, M. Lontano, M. Development Strategies for Fusion Neutron Sources and Subcritical Systems Tardocchi, G. Gorini, A. Botrugno (IT) A.A. Ivanov, A. Krasilnikov (RUS) Fusion Systems R. Goldston, W. Stacey（ USA） Subcritical Fission Systems V. Moiseenko (UA) Level of Readiness of Technologies O. Agren (SE) Key Dates M. Gryaznevich (UK) 15 Jun. 2018 Abstract Submission Deadline H. Ait Abderrahim (BE)
15 Sept. 2018 Online Registration Deadline Y.Wu, Z. Chen, M. Wang, J. Jiang (CN)
29-31 Oct. 2018 Conference Convened Contact Information: Email: [email protected] Contact person: Y. Wang SNINS 1st Symposium on Neutronics and Innovative Nuclear System (SNINS)
An international symposium as an exchange platform on most recent advancements in the neutronics and innovative nuclear systems 25-27 April 2018, Hefei, Anhui, China, hosted by INEST, CAS Conference Topics • Neutron and photon radiation protection and shielding • Radiation source such as tritium • Radiation experiments and measurement technology • Radiation in environment • Strategy and innovative concepts Key Dates Contact Information • 1 March 2018 Abstract Submission Deadline • Email: [email protected] • 15 March 2018 Online Registration Deadline • Tel: +86-551-65593681 • 25-27 April 2018 Conference Convened • Fax: +86-551-65593681
Website: www.fds.org.cn E-mail: [email protected]